ML20072J834
| ML20072J834 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 06/24/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8306300245 | |
| Download: ML20072J834 (2) | |
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TENNESSEE VALLEY AUTHOF{JQRC FM q jg g c W 57tH& M t'5YFEBBE odd
- JEbb lA June 24,E3JUN27 P l l ll BLRD-50-438/81-24 BLRD-50-439/81-26 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - ANALYSIS FOR LOSS OF FEEDWATER EVENT - BLRD-50-438/81-24, BLRD-50-439/81 FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector J. Crlenjak on March 16, 1981 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8102. This was followed by our interim reports dated April 13 and November 16, 1981, March 3, and October 5, 1982 and February 16, 1983 Enclosed is our final report. TVA does not now consider the subject nonconforming condition adverse to the safe operation of the plant.
Therefore, we will amend our records to delete the subject nonconformance as a 10 CFR 50 55(e) item.
If you have any questions concerning this matter, please get in touch with R. II. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, danager l
Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 l
Atlanta, Georgia 30339 Babcock & Wilcox Co. (Enclosure)
P.O. Box 1260 Lynchburg, Virginia 24505 OFFICIAL col'Y Attention:
Mr. R. J. Ansell 8306300245 830624 1
PDR ADOCK 05000438 L 1 S
PDR An Equal Opportunity Employer
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 ANALYSIS FOR LOSS OF PEEDWATER EVENT NCR BLN NEB 8102 BLRD-50-438/81-24, BLRD-50-439/81-26 10 CPR 50.55(e)
FINAL REPORT Description of Deficiency The Bellefonte Final Safety Analysis Report (FSAR) analysis for the loss of normal feedwater event (section 15.2.7) may not be conservative. The Bellefonte FSAR analysis predicts that the ASME Section III Code limits for overpressurization of the Reactor Coolant System (RES) will not be exceeded following a loss of normal feedwater. The Babcock and Wilcox (B&W) Company has performed a more recent analysis foi Ene Washingtor. Public Power Supply System (WPPSS) which predicts that the ASME Code limits for overpressurization will be exceeded following a loss of feedwater (LOFW).
A B&W representative stated, during a March 12, 1981 meeting of the B&W Nonoperating Owners Group, that B&W analysts had reason to suspect a nonconservatism in the B&W computer codes when the Bellefonte analyses were being performed. B&W has several computer codes, including " POWER TRAIN,"
"CADDS," and " TRAP 2," which can be used to predict Reactor Coolant System The pressure following a decrease in heat removal by the secondary system.
computer code "CADDS" was used by B&W for the Bellefonte loss of feedwater analyses. Apparently, "CADDS" predicts a lower Reactor Coolant System pressure than one or more of the other computer codes available to B&W.
TVA notes that the NRC has also raised a concern about the adequacy of "CADDS" in NUREG-0560.
This nonconformance report (NCR) was deemed reportable because if a nonconservative computer analysis was used in this instance a potential exists for overpressurization of the Reactor Coolant System. This NCR also indicates a possible failure of B&W's Quality Assurance program to resolve a known discrepancy in the analyses used to calculate Reactor Coolant System pressure following an LOFW.
Safety Implications TVA has reviewed B&W's Overpressure Protection Report (No. 86-1132936.00) and concurs that the LOFW analysis described in this report is conservative and acceptable. Thus, no potential condition exists for overpressuring the RCS. Therefore, there are no safety implications to Bellefonte, and TVA no longer considers this item to be reportable under 10 CFR 50.55(e).
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